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Prioritizing pressure drop research in nuclear thermal hydraulics
Q Cai, F D'Auria, K Umminger, D Bestion… - Progress in Nuclear …, 2022 - Elsevier
Prediction of pressure drop by wall friction and at geometric discontinuities is important in
nuclear thermal hydraulics simulation. Pressure-drop models were established and …
nuclear thermal hydraulics simulation. Pressure-drop models were established and …
Research progress on thermal hydraulic characteristics of spent fuel pools: A review
C Xu, Z Wang, S Tang, X Chi, X Zhu, Y Li, N Wang - Energies, 2023 - mdpi.com
Nuclear power plants (NPPs) produce large amounts of spent fuel while generating
electricity. After the spent fuel is taken out of the reactor core, it still has a high decay heat …
electricity. After the spent fuel is taken out of the reactor core, it still has a high decay heat …
Modelling fuel assembly flow nozzles in a spent nuclear fuel dry cask using CFD codes
A Hernandez-Avellaneda, G Jimenez, L Rey… - Annals of Nuclear …, 2023 - Elsevier
Abstract Computational Fluid Dynamic (CFD) codes are a widely used tool in spent nuclear
fuel dry storage systems applications. A recurrent simplification used in most spent nuclear …
fuel dry storage systems applications. A recurrent simplification used in most spent nuclear …
Evaluation of existing correlations and development of a new correlation for single-phase friction factor in rod bundle assembly
VS Chalgeri, X Shen, T Yamamoto - Annals of Nuclear Energy, 2024 - Elsevier
Single-phase water flow in rod bundles plays a crucial role in removing the heat generated
in the nuclear reactor core. The design and safety analysis of light-water nuclear reactors …
in the nuclear reactor core. The design and safety analysis of light-water nuclear reactors …
Development of friction factor correlations for hexagonal and square bundles with rough rods based on CFD
Abstract Changes in fuel assembly roughness caused by crud deposits can influence the
flow resistance characteristics of the fuel assembly. The existing correlations cannot …
flow resistance characteristics of the fuel assembly. The existing correlations cannot …
Experimental study on the natural circulation behavior of a full-scale PWR fuel assembly
During a loss-of-coolant accident in spent fuel pools, the fuel assembly will be exposed to
the air environment and decay heat will be removed through the natural circulation of air …
the air environment and decay heat will be removed through the natural circulation of air …
Investigation on turbulent heat transfer to lead-bismuth eutectic flows in rough rod bundles for nuclear applications
X Wang, M Liu, R Zhang, J Fu, T Cong, H Gu - International Journal of …, 2024 - Elsevier
Liquid lead-bismuth eutectic corrosion and the deposition of corrosion particles can lead to
surface roughening of rod bundles, which impacts the convective heat transfer …
surface roughening of rod bundles, which impacts the convective heat transfer …
Natural convection through and over a heating porous medium: Towards high fidelity simulations of nuclear spent fuel pools
V Hamtiaux, P Ruyer, Y Bartosiewicz - … Journal of Heat and Fluid Flow, 2025 - Elsevier
This paper presents a numerical investigation involving Direct Numerical Simulations (DNS)
of natural convection occurring within mixed domains of porous and pure fluids, featuring an …
of natural convection occurring within mixed domains of porous and pure fluids, featuring an …
Development of analytical models for the natural circulation behavior of a full-scale PWR fuel assembly
During a loss-of-coolant accident in spent fuel pools, the fuel assembly will be exposed to
the air environment and decay heat will be removed through the natural circulation of air. In …
the air environment and decay heat will be removed through the natural circulation of air. In …
Development of Nusselt number and friction factor models for rough rod bundles based on wall functions
X Wang, M Liu, X Yan, T Cong, H Gu - Annals of Nuclear Energy, 2024 - Elsevier
The fuel assembly in the reactor undergo surface roughening due to fouling deposits and
material corrosion, which significantly impact the pressure drop and convective heat transfer …
material corrosion, which significantly impact the pressure drop and convective heat transfer …